EP0829088B1 - Absorptionsstruktur zur absorption von neutronen sowie verfahren zur herstellung einer absorptionsstruktur - Google Patents
Absorptionsstruktur zur absorption von neutronen sowie verfahren zur herstellung einer absorptionsstruktur Download PDFInfo
- Publication number
- EP0829088B1 EP0829088B1 EP96914858A EP96914858A EP0829088B1 EP 0829088 B1 EP0829088 B1 EP 0829088B1 EP 96914858 A EP96914858 A EP 96914858A EP 96914858 A EP96914858 A EP 96914858A EP 0829088 B1 EP0829088 B1 EP 0829088B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- absorption
- absorption structure
- cavities
- sheets
- neutron absorbing
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/40—Arrangements for preventing occurrence of critical conditions, e.g. during storage
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the invention relates to an absorption structure for absorption of neutrons, such as those of fuel elements a nuclear reactor, and a process for Production of such an absorption structure.
- absorber parts in the form of various types Manholes, canisters or similar configurations, that surround a neutron emitting object and thereby shield him.
- the use of such absorber parts enables, for example, the compact storage of neutrons Components, in particular fuel elements, from nuclear reactors.
- EP 0 385 187 A1 describes a fuel assembly storage rack known, with the absorber plates in the assembled state form a number of wells that the fuel assemblies over enclose their entire length.
- the made of absorber sheets or Absorber parts formed shafts have a neutron absorbing Material, e.g. Boron steel or borated sheet on.
- the absorber parts are usually manufactured by that a certain proportion of, for example, about 0.8% by weight Boron is introduced into a molten base metal. A absorber part produced from this melt is then to a shaft, a canister or another Processed container.
- a disadvantage of this boron enrichment however, is that the base material by melting or storing boron above one certain concentration becomes brittle, so that further processing extremely difficult and in special applications is even impossible.
- US Pat. No. 4,218,622 describes a composite neutron absorption part which has a thin carrier film or a thin carrier plate on which a polymer matrix is applied, in which boron carbide particles are embedded. Glass fiber is preferably used as the material of the carrier film or the carrier plate. The boron carbide particles are evenly distributed on the surface of the polymer matrix and a boron concentration of up to 0.1 g / cm 2 is achieved.
- this absorber part has a thickness of up to 7 mm, is in the form of a film or sheet and is suspended between an inner wall and an outer wall.
- a structure for shielding is known from US Pat. No. 3,056,028 Neutron rays known.
- This structure comprises two levels and plates aligned parallel to each other, between which a separate honeycomb-like core structure is arranged.
- a neutron absorbent material introduced in the individual cells of the honeycomb-like core structure.
- the side Openings of the core structure are through the opposite, closed flat sheets. The neutron absorbing material can therefore not escape from the individual cells, and a largely homogeneous distribution is achieved.
- the Structure with the honeycomb-like core structure is manufacturing technology however, only complex to manufacture.
- the invention is therefore based on the object, a simple Specify the absorption structure to be produced with the under Avoiding the stated disadvantages with an intended Application a safe shielding of a neutron emitting Object with a high degree of absorption in the entire area to be shielded even over a longer period of time is guaranteed. Furthermore, the invention is the Task based on a method for producing a corresponding Specify absorption structure.
- the object relating to an absorption structure is achieved according to the invention solved in that a neutron absorbing Material between a first sheet and a second sheet is arranged, the first sheet of webs or bulges has, to which the second sheet is attached, so that a plurality of cavities between the two sheets Recording of the neutron absorbing material is formed.
- one of the sheets has webs or arches, is a particularly simple way of attaching the second sheet these webs or arches, in particular by soldering and Welding, possible. This is particularly because an exact It is not necessary to position the sheets in relation to one another is. Is an exact positioning of the sheets to each other given, so can the second sheet with bulges or webs. The corresponding webs can aligned immediately adjacent to each other and with each other get connected. This creates a Spacing of the sheets reached so that the through the webs and cavities formed cavities have an increased depth.
- the shape and size of a cross-sectional area of the cavities can often by designing the webs or arches can be varied, in particular the cross-sectional area rectangular, for example square, diamond-shaped or honeycomb-shaped, be. Bars or bulges can be cut or Stamping or casting processes on a large industrial scale are simple getting produced.
- the absorption structure is suitable, in particular because of the neutron content, which can be largely adjusted as required absorbent material, for a variety of applications, where neutron shielding is required is.
- the mechanical and thermal stability maintains the absorption structure through the sheets that are known and qualified materials.
- the webs or arches preferably form a lattice structure, the sheets on the opposite Sides of the lattice structure firmly connected to this, in particular soldered or welded.
- the lattice structure can be made of a metallic or ceramic material exist and span voids, their cross-sectional area also available in a wide variety of shapes is.
- the neutron absorbing material is preferred in the Cavities distributed homogeneously. This can be done in the form a powder, a sintered material, in a viscous one Consistency or as a shaped body that matches the shape of the cavity is adapted to be introduced. It can be crystalline or amorphous form and a mixture of both.
- the neutron introduced can also be absorbent Have material in different grain size, whereby the amount per unit volume of neutron absorbing material is variable.
- the neutron absorbing material preferably has Boron, hafnium or gadolinium. This is in the cavity introduced with a binder.
- a binder For example, the boron, Hafnium or gadolinium melted into a base metal, in a plastic or an organic or inorganic glue have been glued together.
- the concentration of the neutron absorbing material in the binder is up to 80 to 90 wt .-%. This is a concentration. for example boron, in the absorption structure achievable, which is significantly higher than in previously used Absorption structures. Such an absorption structure is therefore also used to record and shield neutrons emitting material suitable, which is particularly important in storage of spent fuel is advantageous.
- a particularly homogeneous distribution of the neutron absorbing material in the absorption structure is achieved by a large number of cavities, the cross-sectional area of which is a few square centimeters.
- the cross-sectional area is preferably in a range from 1 to 100 cm 2 , in particular approximately 25 cm 2 . With a square cross-sectional area, this corresponds to an edge length of 10 cm and less.
- An absorption container is preferred from the absorption structure for holding a fuel element of a nuclear reactor educated.
- This absorption container can be through the Sheet metal forming cavities simply and with the prescribed necessary mechanical and thermal resilience produce. Austenitic ones are suitable as material for the sheets Steels as well as zircon or others in nuclear power plant construction approved materials.
- the absorption structure is preferred in a fuel pool of a nuclear reactor Used spent fuel recording. Because of of the high attainable proportion of boron and that at the same time high mechanical and thermal stability of the absorption structure this is also suitable for use in Dry storage for spent fuel elements.
- the on a method of manufacturing an absorption structure object is achieved according to the invention in that that between two sheets a neutron absorbing material, in particular boron, hafnium and / or gadolinium is, the first sheet of webs, bulges or a lattice structure on which it with the second sheet is soldered so that the neutron absorbing material in Cavities included becomes.
- the sheets can be pretreated so that soldering without additional additives in a protective gas atmosphere is feasible. At least one sheet with webs is preferred or curvatures used, with these webs or arches the second essentially flat sheet is soldered on. During a successively progressive soldering process also the cavities remaining between the sheets with neutron absorbing material in a predetermined amount be filled.
- the filling with the neutron absorbing Material is made for example by means of a binder, the the neutron absorbing material holds together as well also an at least provisional bond with the arched Manufactures sheet metal or the lattice structure.
- the binder can if necessary escape almost completely during soldering. By a liquid soldering through the webs or bulges formed cavities is slipping or otherwise Prevents the neutron absorbing material from escaping, so that long-term compression processes the homogeneity of the boron distribution only to an extremely limited extent affect within the absorption structure.
- the absorption structure 1 shown in FIG. 1 forms one Absorption container 1a, which is particularly suitable for holding and for the transport of neutron emitting material, such as spent fuel elements of a nuclear reactor, suitable is.
- the absorption container 1a has a rectangular one Cross-section.
- An outer wall 7 of the absorption container la is formed by four first sheets 3a, each both embossed horizontally and vertically Have curvatures 5b, which in the interior of the absorption container 1a are bent. At the bulges 5b are each assigned second sheets 3b attached to an inner wall 8 form the absorption container 1a.
- the neutron absorbing substance 2 can as a sintered material, a powdery material, a viscous material or a full body.
- the Dome 5b can be stamped or embossed in the respective first sheet 3a have been generated. You can also, for example welded or soldered to the first sheet 3a be.
- the fact that the neutron absorbing substance 2 between the metal sheets are stored loosely but non-stationary, can be any approved material, in particular for the sheets austenitic steel or zircon, with a required mechanical and thermal stability can be used.
- FIG. 2 also shows an absorption structure in a spatial representation 1, through which a plurality of absorption shafts 1b is formed. These absorption shafts 1b serve preferably the inclusion of spent fuel of a nuclear reactor.
- Each absorption shaft 1b has an inner one Wall 8 and an outer wall 7, each by first Sheets 3a and second sheets 3b are formed. Due to the spatial arrangement is in the case of adjacent absorption shafts 1b each the inner wall 8 of an absorption shaft 1b the outer wall 7 of the adjacent absorption shaft 1b.
- Figure 2 shows analogously to Figure 1 vertically and horizontal webs 5a between the first sheets 3a and the respectively assigned second metal sheets 3b. The bridges 5a can be embossed or punched in one of the sheets 3a, 3b have been generated.
- Figure 2 also shows a lattice structure 6, which between a first sheet 3a and a second sheet 3b is arranged.
- the corresponding sheets 3a and 3b are soldered or welded to the lattice structure 6, so that through the lattice structure 6 and attached to it Sheets 3a, 3b cavities 4 are formed in the one Neutron absorbing substance 2 is introduced.
- the lattice structure 6 can be made of the same, in particular metallic, Material such as the sheets 3a, 3b be made. It is also possible to make the lattice structure 6 from a different material, for example, a ceramic material.
- the cross-sectional area and thus the shape of the cavities 4 is within wide limits through the arrangement and course of the Ridges 5a, curvatures 5b or the lattice structure 6 can be varied.
- Neutron absorbing substance 2 in any concentration can be introduced so that the absorption capacity of the absorption structure 1 within wide limits and for a wide variety of applications can be interpreted.
- the invention is characterized by an absorption structure which contains a neutron absorbing substance which stored between a first plate and a second plate is.
- the sheets are connected to each other so that between them a plurality of cavities for receiving the Neutron absorbing substance is formed, creating a homogeneous distribution of the neutron absorbing material over ensure the absorption structure over a longer period of time is.
- An abrasion of the neutron absorbing Substance, especially boron, hafnium or gadolinium, and one Dehomogenization is particularly due to the small volume the cavities practically excluded.
- At least one of the Sheet metal has webs or arches caused by embossing, stamping or soldered to it.
- the sheets can be made according to a desired application any approved material, especially one austenitic steel or zircon.
- the absorption structure has a high mechanical and thermal Stability, such as that found in applications the field of nuclear technology, especially in fuel element storage pools and fuel element dry storage.
- the Neutron absorbing material is in the cavities virtually any concentration can be stored, so that too the absorption capacity of the absorption structure in wide Limits depending on the application in a simple way is adjustable.
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Powder Metallurgy (AREA)
Description
- Figur 1
- eine einen Absorptionsbehälter bildende Absorptionsstruktur in einer räumlichen Darstellung sowie
- Figur 2
- eine eine Mehrzahl von Absorptionsschächten bildende Absorptionsstruktur in einer räumlichen Darstellung.
Claims (10)
- Absorptionsstruktur (1) zur Absorption von Neutronen mit einem Neutronen absorbierenden Material (2), welches zwischen einem ersten Blech (3a) und einem zweiten Blech (3b) angeordnet ist, wobei das erste Blech (3a) Stege (5a) oder Wölbungen (5b) aufweist, an welchen das zweiten Blech (3b) befestigt ist, so daß zwischen den Blechen (3a, 3b) eine Mehrzahl von Hohlräumen (4) zur Aufnahme des Neutronen absorbierenden Materials (2) gebildet ist.
- Absorptionsstruktur (1) nach Anspruch 1,
dadurch gekennzeichnet, daß die Stege (5a) oder Wölbungen (5b) eine Gitterstruktur (6) aufweisen. - Absorptionsstruktur (1) nach Anspruch 1 oder 2,
dadurch gekennzeichnet, daß das Neutronen absorbierende Material (2) in den Hohlräumen (4) jeweils homogen verteilt ist. - Absorptionsstruktur (1) nach einem der vorhergehenden Ansprüche,
dadurch gekennzeichnet, daß das Neutronen absorbierende Material (2) in Form eines Pulvers, in gesinterter Form, in viskoser Form oder als den jeweiligen Hohlraum (4) ausfüllender Formkörper eingebracht ist. - Absorptionsstruktur (1) nach einem der vorhergehenden Ansprüche,
dadurch gekennzeichnet, daß das Neutronen absorbierende Material (2) Bor, Hafnium und/oder Gadolinium aufweist. - Absorptionsstruktur (1) nach Anspruch 5,
dadurch gekennzeichnet, daß das Neutronen absorbierende Material (2) in einem Gemisch mit einem Binder eingebracht ist, wobei der Anteil des Neutronen absorbierenden Materials (2) in dem Gemisch bis zu 90 Gew.-% beträgt. - Absorptionsstruktur (1) nach einem der vorhergehenden Ansprüche,
dadurch gekennzeichnet, daß einer der Hohlräume (4) eine Querschnittsfläche (7) von 1 bis 100 cm2, insbesondere 25 cm2 hat. - Absorptionsstruktur (1) nach einem der vorhergehenden Ansprüche, die einen Absorptionsbehälter (8) zur Aufnahme eines Brennelementes eines Kernreaktors bildet.
- Absorptionsstruktur (1) nach einem der vorhergehenden Ansprüche, angeordnet in einem Brennelement-Lagerbecken eines Kernreaktors.
- Verfahren zur Herstellung einer Absorptionsstruktur (1), dadurch gekennzeichnet, daß zwischen zwei Bleche (3a, 3b) ein Neutronen absorbierendes Material (2) angeordnet wird, wobei das erste Blech (3a) Stege (5a), Wölbungen (5b) oder eine Gitterstruktur (6) aufweist, an denen/der es mit dem zweiten Belch (3b) verlötet wird, so daß das Neutronen absorbierende Material (2) in Hohlräumen (4) eingeschlossen wird.
Applications Claiming Priority (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19519231 | 1995-05-24 | ||
DE19519231 | 1995-05-24 | ||
PCT/DE1996/000838 WO1996037896A1 (de) | 1995-05-24 | 1996-05-13 | Absorptionsstruktur zur absorption von neutronen sowie verfahren zur herstellung einer absorptionsstruktur |
Publications (2)
Publication Number | Publication Date |
---|---|
EP0829088A1 EP0829088A1 (de) | 1998-03-18 |
EP0829088B1 true EP0829088B1 (de) | 1999-11-17 |
Family
ID=7762860
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP96914858A Expired - Lifetime EP0829088B1 (de) | 1995-05-24 | 1996-05-13 | Absorptionsstruktur zur absorption von neutronen sowie verfahren zur herstellung einer absorptionsstruktur |
Country Status (3)
Country | Link |
---|---|
EP (1) | EP0829088B1 (de) |
DE (1) | DE59603679D1 (de) |
WO (1) | WO1996037896A1 (de) |
Families Citing this family (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE19706758A1 (de) * | 1997-02-20 | 1998-05-07 | Siemens Ag | Einrichtung zur Lagerung radioaktiven Materials |
DE19714284C2 (de) * | 1997-04-07 | 2002-03-07 | Framatome Anp Gmbh | Absorberelement zur Neutronenabsorption und Brennelement-Lagergestell sowie neutronenabsorbierender Werkstoff |
DE19937670C2 (de) * | 1999-08-10 | 2003-10-30 | Framatome Anp Gmbh | Verfahren und Vorrichtung zum Austausch verbrauchter Absorberelemente eines Brennelent-Lagergestells |
FR2872955B1 (fr) * | 2004-07-08 | 2006-11-17 | Cogema Logistics Sa | Dispositif de rangement pour le stockage et le transport d'assemblages de combustible nucleaire |
FR2909216B1 (fr) | 2006-11-27 | 2009-02-20 | Tn Int | Dispositif de rangement pour le stockage et/ou le transport d'assemblages de combustible nucleaire |
EP2795625A4 (de) * | 2011-12-22 | 2015-09-02 | Holtec International Inc | Speichersystem für kernbrennstoff |
Family Cites Families (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3056028A (en) * | 1960-05-03 | 1962-09-25 | James T Mattingly | Neutron shielding structure |
DE2638922C2 (de) * | 1976-08-28 | 1986-02-20 | Noell GmbH, 8700 Würzburg | Kammer eines Lagergestells zur Aufnahme eines gebrauchten Brennelements aus Kernkraftwerken |
US4218622A (en) * | 1978-01-17 | 1980-08-19 | The Carborundum Company | Neutron absorbing article and method for manufacture thereof |
US4746487A (en) * | 1981-06-10 | 1988-05-24 | U.S. Tool & Die, Inc. | Storage rack for nuclear fuel assemblies |
ES8705990A1 (es) * | 1984-12-24 | 1987-05-16 | Westinghouse Electric Corp | Un barril para almacenamiento de larga duracion de combus- tible nuclear gastado |
-
1996
- 1996-05-13 DE DE59603679T patent/DE59603679D1/de not_active Expired - Lifetime
- 1996-05-13 EP EP96914858A patent/EP0829088B1/de not_active Expired - Lifetime
- 1996-05-13 WO PCT/DE1996/000838 patent/WO1996037896A1/de active IP Right Grant
Also Published As
Publication number | Publication date |
---|---|
DE59603679D1 (de) | 1999-12-23 |
WO1996037896A1 (de) | 1996-11-28 |
EP0829088A1 (de) | 1998-03-18 |
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